Analysis of the Thermal-Hydraulic Response of the Reactor Cavity Cooling System During Accident Scenarios Using the RELAP5/SCDAPSIM System Code

Abstract

The Reactor Cavity Cooling System (RCCS) is one of the passive safety systems included in the design of Generation IV reactors. The RCCS is designed to remove the heat from the reactor cavity by natural circulation without any human intervention, during normal operations and accident conditions. In this study, a model representing the Texas A&M University 1/23 scaled water-cooled RCCS experimental facility has been prepared using the RELAP5/SCDAPSIM system code. Simulations of steady-state configurations have been performed and compared with the available experimental data to validate the models. Transient simulations were performed to study the thermal-hydraulic behavior of the RCCS under hypothetical accident conditions involving the blockage of selected risers. The results of the simulations provided additional information on the behavior of the RCCS during those accidents.